Status of R&D activities on materials for fusion power reactors

Autor: J.-L. Boutard, Ronald L. Klueh, Akira Kohyama, V. M. Chernov, Richard J. Kurtz, Akihiko Kimura, R. Lässer, Takeo Muroga, E. Diegele, Yucheng Wu, Steven J. Zinkle, Hideki Matsui, K. Abe, S. Jitsukawa, Nadine Baluc, Minh Quang Tran, G.R. Odette, Anton Möslang, B. van der Schaaf, Ju-Hyeon Yu
Rok vydání: 2007
Předmět:
Zdroj: Nuclear Fusion. 47:S696-S717
ISSN: 1741-4326
0029-5515
DOI: 10.1088/0029-5515/47/10/s18
Popis: Current R&D activities on materials for fusion power reactors are mainly focused on plasma facing, structural and tritium breeding materials for plasma facing (first wall, divertor) and breeding blanket components. Most of these activities are being performed in Europe, Japan, the People's Republic of China, Russia and the USA. They relate to the development of new high temperature, radiation resistant materials, the development of coatings that will act as erosion, corrosion, permeation and/or electrical/MHD barriers, characterization of candidate materials in terms of mechanical and physical properties, assessment of irradiation effects, compatibility experiments, development of reliable joints, and development and/or validation of design rules. Priorities defined worldwide in the field of materials for fusion power reactors are summarized, as well as the main achievements obtained during the last few years and the near-term perspectives in the different investigation areas.
Databáze: OpenAIRE